轻水堆乏燃料热处理与氯化处理的热力学比较评价

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Jin-Mok Hur, Hunsuk Im, Chang Hwa Lee
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引用次数: 0

摘要

通过对乏核燃料进行处理,根据其特性分离和收集组成核素,可以减轻乏核燃料的处置负担。本研究以高温热处理除去挥发性裂变产物的轻水反应堆SNF为参考材料,基于热力学平衡计算,对热解处理和氯化处理的处理效率进行了评价和比较。由氧化还原(OR)、电精炼(ER)和电积(EW)组成的热处理不仅能有效地从轻水堆SNF中分离出高衰变热、短寿命裂变产物(FPs),而且还能有效地回收可作为核燃料循环使用的超铀元素(tru)。用NH4Cl氯化,然后用Li2CO3在LiCl-KCl熔盐中沉淀的氯化工艺可以有效地从LWR SNF中分离出高衰变热、短寿命的FPs。本研究提出了一种将热解过程中的EW步骤与氯化过程中的NH4Cl氯化步骤相结合的混合工艺。热力学分析表明,它在高衰变热、短寿命FPs分离和tru组回收方面是有效的,表明它有可能成为减少高放废物处理负担的可行选择。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Comparative thermodynamic assessment of pyroprocessing and chlorination for the treatment of LWR spent nuclear fuel
The disposal burden of spent nuclear fuel (SNF) can be reduced by processing it to separate and collect constituent nuclides based on their characteristics. This study evaluates and compares the treatment efficiencies of pyroprocessing and chlorination, based on thermodynamic equilibrium calculations, using light water reactor (LWR) SNF, from which volatile fission products have been removed through high-temperature heat treatment, as the reference material. Pyroprocessing, consisting of oxide reduction (OR), electrorefining (ER), and electrowinning (EW), was effective not only in separating high-decay-heat, short-lived fission products (FPs) from LWR SNF but also in group recovery of transuranic elements (TRUs) that can be recycled as nuclear fuel. The chlorination process, which involves chlorination with NH4Cl, followed by precipitation with Li2CO3 in LiCl-KCl molten salt, was effective in separating high-decay-heat, short-lived FPs from LWR SNF. A hybrid process integrating the EW step of pyroprocessing and the NH4Cl chlorination step of the chlorination process was proposed in this study. Thermodynamic analysis indicates its effectiveness in high-decay-heat, short-lived FPs separation and group recovery of TRUs, demonstrating its potential as a viable option to reduce the disposal burden of high-level waste.
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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